wbinventor/OpenMC-MGXS
LaTeX source for "Multigroup Cross-Section Generation with the OpenMC Monte Carlo Particle Transport Code" published in Nuclear Technology (2019)
TeX
Issues
- 7
Other Romano comments
#7 opened by paulromano - 3
Need units on fission rates for Fig 3
#6 opened by paulromano - 3
Nelson's comments
#2 opened by nelsonag - 1
Eq. 10 and 11
#5 opened by paulromano - 1
Explanation re: estimators
#4 opened by paulromano